Author: International Topical Meeting on Nuclear Reactor Thermal HydraulicsPublisher:
ISBN:
Category :
Languages : en
Pages : 434
Book Description
Ninth International Meeting on Nuclear Reactor Thermal Hydraulics
Author: International Topical Meeting on Nuclear Reactor Thermal HydraulicsPublisher:
ISBN:
Category :
Languages : en
Pages : 434
Book Description
Proceedings of the 1999 Nureth-9 Conference
Author: Publisher:
ISBN: 9780894486500
Category : Technology & Engineering
Languages : en
Pages :
Book Description
Ninth International Topical Meeting on Nuclear Reactor Thermal Hydraulics 1999 (NURETH-9)
Author: Sixth International Topical Meeting on nuclear reactor thermal hydraulics
Author: International Topical Meeting on nuclear reactor thermal hydraulicsPublisher:
ISBN:
Category :
Languages : en
Pages : 776
Book Description
Seventh International Topical Meeting on Nuclear Reactor Thermal Hydraulics
Author: International Topical Meeting on Nuclear Reactor Thermal HydraulicsPublisher:
ISBN:
Category :
Languages : en
Pages : 378
Book Description
Proceedings of the NURETH-12, 12th International Meeting on Nuclear Reactor Thermal Hydraulics, September 30 - October 4, 2007, Pittsburgh, Pennsylvania, USA.
Author: International Meeting on Nuclear Reactor Thermal HydraulicsPublisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Thermal-Hydraulics of Water Cooled Nuclear Reactors
Author: Francesco D'AuriaPublisher: Woodhead Publishing
ISBN: 0081006799
Category : Technology & Engineering
Languages : en
Pages : 1200
Book Description
Thermal Hydraulics of Water-Cooled Nuclear Reactors reviews flow and heat transfer phenomena in nuclear systems and examines the critical contribution of this analysis to nuclear technology development. With a strong focus on system thermal hydraulics (SYS TH), the book provides a detailed, yet approachable, presentation of current approaches to reactor thermal hydraulic analysis, also considering the importance of this discipline for the design and operation of safe and efficient water-cooled and moderated reactors. Part One presents the background to nuclear thermal hydraulics, starting with a historical perspective, defining key terms, and considering thermal hydraulics requirements in nuclear technology. Part Two addresses the principles of thermodynamics and relevant target phenomena in nuclear systems. Next, the book focuses on nuclear thermal hydraulics modeling, covering the key areas of heat transfer and pressure drops, then moving on to an introduction to SYS TH and computational fluid dynamics codes. The final part of the book reviews the application of thermal hydraulics in nuclear technology, with chapters on V&V and uncertainty in SYS TH codes, the BEPU approach, and applications to new reactor design, plant lifetime extension, and accident analysis. This book is a valuable resource for academics, graduate students, and professionals studying the thermal hydraulic analysis of nuclear power plants and using SYS TH to demonstrate their safety and acceptability. - Contains a systematic and comprehensive review of current approaches to the thermal-hydraulic analysis of water-cooled and moderated nuclear reactors - Clearly presents the relationship between system level (top-down analysis) and component level phenomenology (bottom-up analysis) - Provides a strong focus on nuclear system thermal hydraulic (SYS TH) codes - Presents detailed coverage of the applications of thermal-hydraulics to demonstrate the safety and acceptability of nuclear power plants
International Topical Meeting on Nuclear Reactor Thermal Hydraulics ; 2
Author: International Topical Meeting on Nuclear Reactor Thermal Hydraulics ; 5
Author: Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors
Author: Francesco D'AuriaPublisher: Elsevier
ISBN: 0323856071
Category : Business & Economics
Languages : en
Pages : 932
Book Description
Handbook on Thermal Hydraulics of Water-Cooled Nuclear Reactors, Volume 1, Foundations and Principles includes all new chapters which delve deeper into the topic, adding context and practical examples to help readers apply learnings to their own setting. Topics covered include experimental thermal-hydraulics and instrumentation, numerics, scaling and containment in thermal-hydraulics, as well as a title dedicated to good practices in verification and validation. This book will be a valuable reference for graduate and undergraduate students of nuclear or thermal engineering, as well as researchers in nuclear thermal-hydraulics and reactor technology, engineers working in simulation and modeling of nuclear reactors, and more. In addition, nuclear operators, code developers and safety engineers will also benefit from the practical guidance provided. - Presents a comprehensive analysis on the connection between nuclear power and thermal hydraulics - Includes end-of-chapter questions, quizzes and exercises to confirm understanding and provides solutions in an appendix - Covers applicable nuclear reactor safety considerations and design technology throughout